U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
07/22/2003 - 07/23/2003
** EVENT NUMBERS **
40002 40007 40008 40009 40010 40011
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|General Information or Other |Event Number: 40002 |
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| REP ORG: NE DIV OF RADIOACTIVE MATERIALS |NOTIFICATION DATE: 07/17/2003|
|LICENSEE: HASTINGS STATE BANK |NOTIFICATION TIME: 10:42[EDT]|
| CITY: LINCOLN REGION: 4 |EVENT DATE: 07/17/2003|
| COUNTY: STATE: NE |EVENT TIME: [CDT]|
|LICENSE#: GL0377 AGREEMENT: Y |LAST UPDATE DATE: 07/17/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |MATT HAHN IAT |
+------------------------------------------------+JOHN GREEVES NMSS |
| NRC NOTIFIED BY: TRUDY HILL | |
| HQ OPS OFFICER: HOWIE CROUCH | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|BLO1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
| | |
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EVENT TEXT
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| AGREEMENT STATE REPORT - TWO LOST EXIT SIGNS THAT CONTAIN TRITIUM |
| |
| At 1042 EDT on 7/17/03, a Nebraska Radiation Program Radiation Health |
| Specialist reported that a licensee, Hastings State Bank, could not account |
| for two tritium-based exit signs. The bank is buying a building that |
| previously housed a bank. Nebraska State Radiation Program billed the new |
| bank for the materials license associated with the exit signs. The new |
| branch manager of the Hastings Bank was unable to locate the exit signs in |
| question. In April of 1989, each sign contained 4.7 curies of tritium. The |
| State of Nebraska will be visiting the site when the new bank opens in |
| August. |
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|Power Reactor |Event Number: 40007 |
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| FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 07/22/2003|
| UNIT: [3] [] [] STATE: LA |NOTIFICATION TIME: 11:13[EDT]|
| RXTYPE: [3] CE |EVENT DATE: 07/21/2003|
+------------------------------------------------+EVENT TIME: 14:15[CDT]|
| NRC NOTIFIED BY: MIKE BRANDON |LAST UPDATE DATE: 07/22/2003|
| HQ OPS OFFICER: HOWIE CROUCH +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |TROY PRUETT R4 |
|10 CFR SECTION: | |
|HFIT 26.73 FITNESS FOR DUTY | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|3 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| FITNESS FOR DUTY |
| |
| A Senior Reactor Operator licensed individual was determined to be under the |
| influence of illegal drugs during a random test. The employee's access to |
| the plant has been terminated. Contact the HOO for additional details. |
| |
| The NRC Resident Inspector has been notified. |
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|Power Reactor |Event Number: 40008 |
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| FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 07/22/2003|
| UNIT: [1] [] [] STATE: MN |NOTIFICATION TIME: 16:10[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 07/22/2003|
+------------------------------------------------+EVENT TIME: 09:48[CDT]|
| NRC NOTIFIED BY: GERRY STOCKHAM |LAST UPDATE DATE: 07/22/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE MARIE STONE R3 |
|10 CFR SECTION: | |
|AINA 50.72(b)(3)(v)(A) POT UNABLE TO SAFE SD | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
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EVENT TEXT
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| HELB DOOR NOT LATCHED AS REQUIRED DUE TO PERSONNEL ERROR |
| |
| "A High Energy Line Break (HELB) door was not latched as required. This |
| condition is being reported as an event that could have prevented the |
| fulfillment of a safety function in accordance with 10CFR50.72(b)(3)(v)(A). |
| The door is currently closed." |
| |
| The HELB door which separates two critical Motor Control Center [MCC] areas |
| was unlatched for less than two (2) minutes. The licensee will inform the |
| state representative and has informed the NRC resident inspector. |
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|Power Reactor |Event Number: 40009 |
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| FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 07/22/2003|
| UNIT: [1] [2] [] STATE: AL |NOTIFICATION TIME: 17:24[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/22/2003|
+------------------------------------------------+EVENT TIME: 14:56[CDT]|
| NRC NOTIFIED BY: DANA WHITE |LAST UPDATE DATE: 07/22/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |ANNE BOLAND R2 |
|10 CFR SECTION: | |
|APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
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EVENT TEXT
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| OFFSITE NOTIFICATION TO OTHER GOVERNMENT AGENCIES CONCERNING MINOR OIL |
| SPILL |
| |
| "On 7-22-03 at 1100, approximately 1 gallon of fuel oil was spilled during a |
| diesel generator fuel oil transfer surveillance test due to a leak at a hose |
| connection. It is estimated that 1 quart of fuel oil went into a nearby |
| floor drain. As a result, a visible sheen of oil was observed on a swamp |
| area on plant site. This is a reportable spill to government agencies since |
| there is a visible sheen on "waters of the United States". The US Coast |
| Guard National Response Center was notified at 1456 on 7/22/03 and the |
| Alabama Department of Environmental Management was notified at 1510 on |
| 7/22/03." |
| |
| The licensee informed the NRC Resident Inspector. |
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|Power Reactor |Event Number: 40010 |
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| FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 07/22/2003|
| UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 17:33[EDT]|
| RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 07/22/2003|
+------------------------------------------------+EVENT TIME: 13:45[EDT]|
| NRC NOTIFIED BY: TODD STRAYER |LAST UPDATE DATE: 07/22/2003|
| HQ OPS OFFICER: STEVE SANDIN +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: NON EMERGENCY |DANIEL HOLODY R1 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| |
|AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 A/R Y 100 Power Operation |0 Hot Shutdown |
| | |
| | |
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EVENT TEXT
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| AUTOMATIC REACTOR SCRAM DUE TO MAIN GENERATOR PROTECTIVE RELAY ACTUATION |
| |
| "With Unit 2 operating at 100% power, a Main Generator protective relay |
| actuation occurred causing a Main Turbine trip and automatic Reactor |
| Protection System (RPS) actuation. The RPS signal received was Main Turbine |
| Control Valve Fast Closure. RPS functioned as designed and all control rods |
| fully inserted. Group II and III primary containment isolations went to |
| completion and Standby Gas Treatment automatically started when reactor |
| level reached the setpoint of 1" reactor level. |
| |
| "At 1358, with Standby Gas Treatment System in operation, Main Steam Tunnel |
| temperatures rose to the Group I isolation setpoint and a Group I isolation |
| occurred. There was not a steam leak that caused the Group I isolation. |
| Following the Group I isolation, reactor level again lowered to the 1" RPS |
| actuation and Group II/III isolation setpoint. All control rods were fully |
| inserted when this RPS actuation occurred. With containment isolated, HPCI |
| and RCIC were used to control reactor level. |
| |
| "At 1615 hours, while transitioning reactor level control to condensate, a |
| RPS actuation, Group II, and Group III isolation occurred when reactor level |
| reached the setpoint of 1". All control rods were fully inserted at the |
| time. All containment isolation valves that were opened following the |
| initial actuation, isolated as expected. |
| |
| "All primary containment parameters are currently normal. The crew has |
| stabilized the plant and plant recovery actions have commenced. The cause |
| of the Main Generator protective relay actuation is not known at this |
| time." |
| |
| The licensee notified the NRC Resident Inspector. |
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|General Information or Other |Event Number: 40011 |
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| REP ORG: THERMO ELECTRON CORPORATION |NOTIFICATION DATE: 07/22/2003|
|LICENSEE: THERMO ELECTRON CORPORATION |NOTIFICATION TIME: 18:13[EDT]|
| CITY: HOUSTON REGION: 4 |EVENT DATE: 05/30/2003|
| COUNTY: STATE: TX |EVENT TIME: [CDT]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 07/22/2003|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DANIEL HOLODY R1 |
| |ANNE BOLAND R2 |
+------------------------------------------------+KRISS KENNEDY R4 |
| NRC NOTIFIED BY: BARRY NICHOLSON |JACK FOSTER NRR |
| HQ OPS OFFICER: NATHAN SANFILIPPO | |
+------------------------------------------------+ |
|EMERGENCY CLASS: NON EMERGENCY | |
|10 CFR SECTION: | |
|CCCC 21.21 UNSPECIFIED PARAGRAPH | |
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| | |
| | |
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EVENT TEXT
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| PART 21 NOTIFICATION DUE TO POSSIBLE DEFECT WITH THERMO WESTRONICS SERIES |
| 2100C RECORDERS |
| |
| The following report was received via fax: |
| |
| "July 21, 2003 |
| |
| "Subject: Thermo Westronics Model 2100C Series Recorders |
| |
| "This letter is notification of a possible defect associated with Thermo |
| Westronics Series 2100C recorders. The Series 2100C is a DIN size |
| programmable chart recorder utilized in control room applications of Nuclear |
| Power Plants. The recorders in question were manufactured under the Thermo |
| Westronics 10CFR50 Appendix B Quality Program between August 2002 and |
| January 2003. |
| |
| "On or about May 30, 2003, Thermo Electron determined that a random reset |
| anomaly could possibly occur on the Series 2100C recorder. This anomaly |
| surfaced during the manufacture of three (3) commercial grade Series 2100 |
| recorders. When the reset occurs, the recorder must be re-initialized to |
| resume normal function. |
| |
| "The root cause of the anomaly has been traced to a timing issue between the |
| CPU Printed Circuit Board Assembly (PCBA) and the Memory Module. A 27C256 |
| EPROM, used as a decoder on the Memory Module, has changed manufacturers |
| several times during the life of this product. The EPROM as produced by the |
| original manufacturer is no longer available. |
| |
| "Newer versions of this 27C256 EPROM typically function at faster speeds. |
| The faster chip speed can cause a delay in the transition from "send" to |
| "receive"' on the CPU Module and thereby result in the reset. This reset |
| event is random and does not occur on every recorder. |
| |
| "After engineering evaluation, Thermo Electron has incorporated a |
| modification to the CPU PCBA to ensure compatibility with the faster EPROM |
| on the Memory Module. This modification eliminates the timing delay and |
| subsequent possibility of the reset. Future shipments of this CPU Module |
| shall incorporate this modification. |
| |
| "To ensure compatibility on previously installed recorders, the Memory |
| Module shall only be offered as part of a kit that includes the newer |
| version CPU PCBA. |
| |
| "The scope of this notification includes ten (10) Series 2100C safety |
| related recorders, all of which were thoroughly tested and did not exhibit |
| this reset at the time of shipment. However, since it is not possible to |
| determine the exact manufacture date of the 27C256 EPROM used on these |
| recorders, this notification is being issued. |
| |
| . |
| . [Table removed] |
| . |
| |
| "Thermo Electron shall notify listed customers and make arrangements to |
| implement the design modification, either by rework at the Thermo Electron - |
| Houston facility, or by providing replacement kits to the customer site. It |
| is estimated that rework associated with the design modification should be |
| completed within sixty (60) days, or as soon as Thermo Electron has been |
| contacted by the identified customers." |
| |
| The affected sites include Laguna Verde, Mexico, Millstone, Catawba, and |
| McGuire. |
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